Analysis of post boiling transition heat transfer (Development and evaluation for prediction method of fuel rod wall temperature)

Mitsuru Yamada, Shinichi Morooka

    Research output: Contribution to journalArticle

    Abstract

    From the viewpoint of safety design of nuclear reactor and an economic terms, It is important to clear the mechanism of post boiling transition heat transfer and to estimate correctly the fuel rod wall temperature. So, in this research, we proposed a calculation model of post boiling transition heat transfer and developed a method to predict the axial variation of the fuel rod wall temperature. Furthermore, we evaluated the prediction accuracy and validity of this prediction method by comparing the prediction results with experimental data for a circular tube measured by Bennett et al (1) under the actual BWR's operating conditions. From the results, it was concluded that under high pressure (7MPa) and for a wide range of conditions, the method developed in this research was able to predict accurately.

    Original languageEnglish
    Pages (from-to)2301-2311
    Number of pages11
    JournalNihon Kikai Gakkai Ronbunshu, B Hen/Transactions of the Japan Society of Mechanical Engineers, Part B
    Volume79
    Issue number806
    DOIs
    Publication statusPublished - 2013

    Fingerprint

    wall temperature
    boiling
    Boiling liquids
    rods
    heat transfer
    Heat transfer
    evaluation
    predictions
    circular tubes
    nuclear reactors
    Nuclear reactors
    Temperature
    economics
    safety
    Economics
    estimates

    Keywords

    • BWR
    • Heat transfer
    • Post boiling transition
    • POST-BT

    ASJC Scopus subject areas

    • Mechanical Engineering
    • Condensed Matter Physics

    Cite this

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    abstract = "From the viewpoint of safety design of nuclear reactor and an economic terms, It is important to clear the mechanism of post boiling transition heat transfer and to estimate correctly the fuel rod wall temperature. So, in this research, we proposed a calculation model of post boiling transition heat transfer and developed a method to predict the axial variation of the fuel rod wall temperature. Furthermore, we evaluated the prediction accuracy and validity of this prediction method by comparing the prediction results with experimental data for a circular tube measured by Bennett et al (1) under the actual BWR's operating conditions. From the results, it was concluded that under high pressure (7MPa) and for a wide range of conditions, the method developed in this research was able to predict accurately.",
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    AU - Morooka, Shinichi

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    N2 - From the viewpoint of safety design of nuclear reactor and an economic terms, It is important to clear the mechanism of post boiling transition heat transfer and to estimate correctly the fuel rod wall temperature. So, in this research, we proposed a calculation model of post boiling transition heat transfer and developed a method to predict the axial variation of the fuel rod wall temperature. Furthermore, we evaluated the prediction accuracy and validity of this prediction method by comparing the prediction results with experimental data for a circular tube measured by Bennett et al (1) under the actual BWR's operating conditions. From the results, it was concluded that under high pressure (7MPa) and for a wide range of conditions, the method developed in this research was able to predict accurately.

    AB - From the viewpoint of safety design of nuclear reactor and an economic terms, It is important to clear the mechanism of post boiling transition heat transfer and to estimate correctly the fuel rod wall temperature. So, in this research, we proposed a calculation model of post boiling transition heat transfer and developed a method to predict the axial variation of the fuel rod wall temperature. Furthermore, we evaluated the prediction accuracy and validity of this prediction method by comparing the prediction results with experimental data for a circular tube measured by Bennett et al (1) under the actual BWR's operating conditions. From the results, it was concluded that under high pressure (7MPa) and for a wide range of conditions, the method developed in this research was able to predict accurately.

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